MissionIntegrity assessment of nuclear reactor internals and of components of the primary coolant system, as well as of embrittlement of pressure vessel steels.
Development of small specimen test techniques, non-destructive methods, and analytical and numerical analysis to determine materials properties evolution in harsh environments.
Teaching for the Master in Nuclear Engineering and education of young scientists in the field of nuclear materials and fuel.
BiographyPhilippe Spätig is currently Adjunct Professor at EPFL in the School of Basic Sciences, in the Laboratory of Reactor Physics and Systems Behaviours. He obtained his diploma of Engineer Physicist at EPFL in 1991 and his PhD at EPFL in 1995 on the role of thermal activation in the plasticity of the intermetallic Ni3Al.
From 1995 to 1997, he worked as postdoc in the Materials Group of the Center for Research in Plasma Physics at EPFL, studying the effects of high-energy proton irradiation on alloys and pure metals. He then moved to the University of California Santa Barbara and spent two years in the group of Professor G.R. Odette, working on fracture mechanics of ferritic structural steels.
He joined again the Materials Group of the Center for Research in Plasma Physics at EPFL in 2000 and worked in this group until the end of 2012. His research was focused on irradiation hardening and embrittlement of steels, as well as on the development of oxide dispersion strengthened steels. He also worked and developed experimental and analytical small specimen test techniques to reliably extract mechanical properties from limited material volume.
In 2013, he joined the Laboratory for Nuclear Materials at Paul Scherrer Institute, while being associated with the Laboratory for Reactor Physics and System Behaviours at EPFL. Since then he mainly works on environmentally-assisted fatigue and fracture on austenitic and pressure vessel steels, where the effects of light water reactor environment on mechanical properties are investigated.
EPFL - Switzerland
EPFL - Switzerland
Protein Engineering for Personalized therapy and diagnosisLausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-8705.
Role of mean stress on fatigue behavior of a 316L austenitic stainless steel in LWR and air environmentsInternational Journal Of Fatigue. 2021-04-01. DOI : 10.1016/j.ijfatigue.2020.106111.
Characterization of Austenitic Stainless Steels with Regard to Environmentally Assisted Fatigue in Simulated Light Water Reactor ConditionsMetals. 2021-02-01. DOI : 10.3390/met11020307.
Dynamic study of contact damping in martensitic stainless steels using nano-indentationMechanics Of Materials. 2020-10-01. DOI : 10.1016/j.mechmat.2020.103541.
Mean Stress Effect on Fatigue Behavior of Austenitic Stainless Steel in Air and LWR ConditionsMechanical Fatigue of Metals; Springer, Cham, 2019-05-08. p. 386.
Evaluation of Quasi-Static and Dynamic Fracture Toughness on the Low-Alloy Reactor Pressure Vessel Steel JRQ in the Transition Region2019-12-13. 18th International Conference on Fracture and Damage Mechanics. p. 294-299. DOI : 10.4028/www.scientific.net/KEM.827.294.
Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environmentsCorrosion Science. 2019-05-15. DOI : 10.1016/j.corsci.2019.03.013.
Environmental degradation of fracture resistance in high-temperature water environments of low-alloy reactor pressure vessel steels with high sulphur or phosphorus contentsCorrosion Science. 2019-07-01. DOI : 10.1016/j.corsci.2019.04.011.
Ferritic and Tempered Martensitic SteelsStructural alloys for nuclear energy applications; Elsevier, 2019. p. 485-527.
Deformation twinning in irradiated ferritic/martensitic steelsJournal of Nuclear Materials. 2018-04-01. DOI : 10.1016/j.jnucmat.2018.01.057.
Evaluation of mechanical properties of irradiated zirconium alloys in the vicinity of the metal-oxide interfaceMaterials Science and Engineering:. 2018-10-01. DOI : 10.1016/j.msea.2018.09.107.
Influence of mean stress and light water reactor environment on fatigue life and dislocation microstructures of 316L austenitic steelJournal of Nuclear Materials. 2018-05-28. DOI : 10.1016/j.jnucmat.2018.05.064.
Helium effects on IASCC susceptibility in as-implanted solution annealed, cold-worked and post-implantation annealed 316L steelCorrosion Engineering, Science and Technology. 2017-02-09. DOI : 10.1080/1478422X.2017.1323709.
Effect of residual stresses on notch toughness of the tempered martensitic steel F82H-MODTheoretical and Applied Fracture Mechanics. 2017-05-26. DOI : 10.1016/j.tafmec.2017.05.023.
Microstructure and tensile properties of ODS ferritic steels mechanically alloyed with Fe 2 YNuclear Materials and Energy. 2016. DOI : 10.1016/j.nme.2016.09.019.
An inverse method based on finite element model to derive the plastic flow properties from non-standard tensile specimens of Eurofer97 steelNuclear Materials and Energy. 2016. DOI : 10.1016/j.nme.2016.06.017.
Effect of high-temperature water and hydrogen on the fracture behavior of a low-alloy reactor pressure vessel steelJournal of Nuclear Materials. 2016. DOI : 10.1016/j.jnucmat.2016.05.033.
Investigation of microstructure and microhardness of pure W and W-2Y(2)O(3) materials before and after ion-irradiationInternational Journal Of Refractory Metals & Hard Materials. 2014. DOI : 10.1016/j.ijrmhm.2014.06.004.
Measurement of residual stresses around the notch of tensile specimens of the high-Cr tempered martensitic steel F82H-mod2014. 7th International Conference on Materials Structure and Micromechanics of Fracture (MSMF 7), Brno, CZECH REPUBLIC, JUL 01-03, 2013. p. 295-298. DOI : 10.4028/www.scientific.net/KEM.592-593.295.
Analytical determination of the constitutive behavior from micro-pillar testing: Application to a tempered martensitic steelAip Advances. 2014. DOI : 10.1063/1.4873155.
Measurement of residual stresses around the notch of tensile specimens of the high-Cr tempered martensitic steel F82H-mod2014. p. 295-298.
Microstructure and mechanical properties of a W-2wt.%Y2O3 composite produced by sintering and hot forgingJournal Of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.301.
On determination of the constitutive behavior of tempered martensitic steels from micro-indentations: Application to Eurofer97 steelJournal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.003.
Helium embrittlement of a lamellar titanium aluminideJournal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2012.11.031.
Fracture toughness characterization in the lower transition of neutron irradiated Eurofer97 steelJournal of Nuclear Materials. 2013. DOI : 10.1016/j.jnucmat.2013.01.002.
Effect of warm pre-stressing on fracture toughness of Eurofer97 steel2013. 27th Symposium on Fusion Technology (SOFT), Liège, Belgium, September 24-28, 2012. p. 644-647. DOI : 10.1016/j.fusengdes.2013.05.056.
Effect of ion-irradiation on the microstructure and microhardness of the W-2Y(2)O(3) composite materials fabricated by sintering and hot forging2013. 27th Symposium on Fusion Technology (SOFT). p. 1668-1672. DOI : 10.1016/j.fusengdes.2013.03.060.
Nanocomposites of carbon nanotubes embedded in a (Ti,Al)N coated filmSurface & Coatings Technology. 2012. DOI : 10.1016/j.surfcoat.2012.09.053.
W-2 wt.%Y2O3 composite: Microstructure and mechanical propertiesMaterials Science And Engineering A-Structural Materials Properties Microstructure And Processing. 2012. DOI : 10.1016/j.msea.2012.01.011.
Effect of thermo-mechanical treatments on the microstructure and mechanical properties of an ODS ferritic steelJournal Of Nuclear Materials. 2011. DOI : 10.1016/j.jnucmat.2011.03.006.
Strain-rate behavior in tension of the tempered martensitic reduced activation steel Eurofer97Journal Of Nuclear Materials. 2011. DOI : 10.1016/j.jnucmat.2011.05.002.
From Materials Development to their Test in IFMIF: an Overview2010. 23rd IAEA Fusion Energy Conference, Daejon, Korea, 11-16 October 2010.
Fracture toughness master-curve analysis of the tempered martensitic steel Eurofer972009. 13th International Conference on Fusion Reactor Materials (ICFRM-13), Nice, France, December 10-14, 2007. p. 323-327. DOI : 10.1016/j.jnucmat.2008.12.122.
Recent progress toward development of reduced activation ferritic/martensitic steels for fusion applications2009. 13th International Conference on Fusion Reactor Materials, Nice, France, December 10-14, 2007. p. 411-417. DOI : 10.1016/j.jnucmat.2008.12.323.
Assessment of irradiation embrittlement of the Eurofer97 steel after 590 MeV proton irradiation2009. 13th International Conference on Fusion Reactor Materials, Nice, France, December 10-14, 2007. p. 245-248. DOI : 10.1016/j.jnucmat.2008.12.110.
Numerical investigation by finite element simulations of the ball punch test: Application to tempered martensitic steels2009. 13th International Conference on Fusion Reactor Materials, Nice, France, December 10-14, 2007. p. 319-322. DOI : 10.1016/j.jnucmat.2008.12.120.
Fracture properties of notched and pre-cracked specimens of a tempered martensitic steel at low temperature2008. 14th International Conference on the Strength of Materials (ICSMA 14), Xian, PEOPLES R CHINA, June 4-9, 2006. p. 346-349. DOI : 10.1016/j.msea.2006.09.172.
Analysis of high temperature deformation mechanism in ODS EUROFER97 alloy2008. Symposium on Microstructural Processes in Irradiated Materials held at the 2007 TMS Annual Meeting, Orlando, FL, USA, February 25 - March 1, 2007. p. 210-216. DOI : 10.1016/j.jnucmat.2008.08.009.
The evolution of the mobile dislocation density during successive stress relaxation transientsMaterials Science and Engineering A. 2008. DOI : 10.1016/j.msea.2006.10.196.
Fracture toughness behavior in the ductile-brittle transition region of the tempered martensitic Eurofer97 steel: Experiments and modelingEngineering fracture mechanics. 2008. DOI : 10.1016/j.engfracmech.2008.01.016.
A multiscale approach to measuring and modeling cleavage fracture in structural steelsMaterials Issues for Generation IV Systems; Dordrecht, The Netherlands: Springer, 2008. p. 203-226.
Fracture toughness properties in the transition region of the Eurofer97 tempered martensitic steelJournal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.03.031.
The role of small specimen test technology in fusion materials developmentJournal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.04.034.
Plastic flow properties and fracture toughness characterization of unirradiated and irradiated tempered martensitic steelsJournal of Nuclear Materials. 2007. DOI : 10.1016/j.jnucmat.2007.03.038.
The European effort towards the development of a demo structural material: Irradiation behaviour of the European reference RAFM steel EUROFERFusion Engineering and Design. 2006. DOI : 10.1016/j.fusengdes.2005.08.044.
On the strain-hardening of tempered martensitic alloysMaterials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 2005. DOI : 10.1016/j.msea.2004.12.056.
Assessment of irradiation-hardening on Eurofer97' and Zircaloy 2 with punch tests and finite-element modelingMaterials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 2005. DOI : 10.1016/j.msea.2005.02.088.
Deformation behaviour and microstructure of nanocrystalline electrodeposited and high pressure torsioned nickelActa Materialia. 2005. DOI : 10.1016/j.actamat.2005.01.041.
Mechanical behaviour of nanocrystalline electrodeposited Ni above room temperatureScripta Materialia. 2005. DOI : 10.1016/j.scriptamat.2005.03.026.
Dislocation defect interaction in irradiated CuMaterials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 2005. DOI : 10.1016/j.msea.2005.03.093.
Assessment of plastic flow and fracture properties with small specimen test techniques for IFMIF-designed specimensNuclear Fusion. 2005. DOI : 10.1088/0029-5515/45/7/011.
The tensile properties of irradiated Ni single crystals and their temperature dependencePhilosophical Magazine. 2005. DOI : 10.1080/14786430412331319947.
A master curve analysis of F82H using statistical and constraint loss size adjustments of small specimen dataJournal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.255.
Hardening mechanisms in ferritic/martensitic steels2004. Effects of radiation on materials, Tucson, June 18-20, 2002. p. 341-351.
On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactorsNuclear Fusion. 2004. DOI : 10.1088/0029-5515/44/1/006.
Plastic flow of martensitic model alloysMaterials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 2004. DOI : 10.1016/j.msea.2004.02.074.
Tensile properties of a tempered martensitic iron-chromium- carbon model alloyJournal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.054.
Assessment of the constitutive properties from small ball punch test: experiment and modelingJournal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.07.052.
SANS investigation of proton-irradiated EUROFER97Journal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.052.
Materials design data for reduced activation martensitic steel type EUROFERJournal of Nuclear Materials. 2004. DOI : 10.1016/j.jnucmat.2004.04.020.
Second IEA Fusion Materials Agreement Workshop - Proceedings of the Second IEA Fusion Materials Agreement Workshop on Modeling and Experimental Validation - Les Diableret, Switzerland - September 30-October 4, 2002 - PrefaceJournal of Nuclear Materials. 2003. DOI : 10.1016/j.jnucmat.2003.08.016.
Second IEA fusion materials agreement workshop on modeling and experimental validationJournal of Nuclear Materials. 2003. DOI : 10.1016/j.jnucmat.2003.08.017.
Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82HJournal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01075-9.
Recent progress in small specimen test technologyJournal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01171-6.
Assessment of mechanical properties of the martensitic steel EUROFER97 by means of punch testsJournal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01194-7.
Microstructure and mechanical properties of two ODS ferritic/martensitic steelsJournal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01193-5.
On the mechanical properties of the advanced martensitic steel EUROFER 97Journal of Nuclear Materials. 2002. DOI : 10.1016/S0022-3115(02)01213-8.
Relation between microstructures and constitutive behavior of advanced tempered martensitic steels2001. Mat. Res. Soc. Symposium Proc.: Material Instabilities and Patterning in Metals.
Transition regime fracture toughness-temperature properties of two advanced ferritic/martensitic steels2001. Mat. Res. Soc. Symposium Proc.: on Multiscale modelling of materials. p. Z7.8.1-Z7.8.6. DOI : 10.1557/PROC-653-Z7.8.
Characterising thermally activated dislocatin mechanismsMaterials Science and Engineering A. 2001. DOI : 10.1016/S0921-5093(00)01763-9.
On the constitutive behavior of the F82H ferritic/martensitic steelMaterials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 2001. DOI : 10.1016/S0921-5093(00)01634-8.
Structural materials for fusion reactorsNuclear Fusion. 2001. DOI : 10.1088/0029-5515/41/8/308.
Dislocation core geometry and mechaical strenght in Ni3Al compounds2000. 12th Eureopean Congress on Electron Microscopy (EUREM 12).
Constitutive behavior and fracture toughness properties of the F82H ferritic/martensitic steelJournal of Nuclear Materials. 2000. DOI : 10.1016/S0022-3115(00)00232-4.
The mechanical properties of 590 MeV proton irradiated ironJournal of Nuclear Materials. 1999. DOI : 10.1016/S0022-3115(98)00702-8.
Low temperature yield properties of two 7-9Cr Ferritic/martensitic steelsJournal of Nuclear Materials. 1999. DOI : 10.1016/S0022-3115(99)00121-X.
Impurity segregation investigation in low activation martensitic steels using EFTEM1998. 11th European Congress on Electron Microscopy.
Microstructure assessment of the low activation ferritic/martensitic steel F82HJournal of Nuclear Materials. 1998. DOI : 10.1016/S0022-3115(98)00182-2.
Chemical segregation behavior of the low activation ferritic/martensitic steel F82HJournal of Nuclear Materials. 1998. DOI : 10.1016/S0022-3115(98)00337-7.
Evolution of the mechanical properties of the F82H ferritic/martensitic steel after 590 MeV proton irradiationJournal of Nuclear Materials. 1998. DOI : 10.1016/S0022-3115(98)00397-3.
Deformation microstructures in Ni-3(Al, Hf)Materials Science and Engineering A -Structural Materials Properties Microstructure and Processing. 1997. DOI : 10.1016/S0921-5093(97)00578-9.
Microstructure and mechanical properties of newly developed low activation martensitic steelsJournal of Nuclear Materials. 1996. DOI : 10.1016/S0022-3115(96)00133-X.
Teaching & PhD
Doctoral Program in Physics
Doctoral Program in Materials Science and Engineering